IR 05000443/2013007

Seabrook Station, Unit 1 - NRC Supplemental Inspection Report 0500443-13-007 and Assessment Follow-Up Letter

ML13073A614
Person / Time
Site:	Seabrook
Issue date:	03/15/2013
From:	Anthony Dimitriadis Plant Support Branch 1
To:	Walsh K T NextEra Energy Seabrook
References
IR-13-007
Download: ML13073A614 (17)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 March 15, 2013 Mr. Kevin Walsh Site Vice President Seabrook Nuclear Power Plant NextEra Energy Seabrook, LLC c/o Mr. Michael O'Keefe P.O. Box 300 Seabrook, NH 03874

SUBJECT: SEABROOK STATION, UNIT NO. 1 - NRC SUPPLEMENTAL INSPECTION REPORT 0500443/2013007 AND ASSESSMENT FOLLOW-UP LETTER

Dear Mr. Walsh:

On January 24, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure (IP) 95001, "Inspection for One or Two White Inputs in a Strategic Performance Area," at Seabrook Station, Unit No. 1. The enclosed inspection report (IR) documents the inspection results, which were discussed on January 24, 2013, with you and members of your staff.

In accordance with the NRC Reactor Oversight Process Action Matrix, this supplemental inspection was performed to followup on a White finding of low to moderate safety significance in the second quarter of 2012, that involved the failure of Seabrook Station personnel to carry out their assigned roles and responsibilities and to adequately critique the performance of the April 17, 2012, evaluated emergency preparedness exercise. NextEra responded to the finding by letter dated June 21, 2012. The NRC reviewed the additional information provided and communicated the final significance determination to you in a letter dated August 7, 2012, "Final Significance Determination for a White Finding, with Assessment Follow-up and Notice of Violation, NRC Inspection Report No. 05000443/2012504 - Seabrook Station, Unit 1" (ML12220A471). You informed the NRC on December 1, 2012, of your staff's readiness for this supplemental inspection.

The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the risk-significant issues were understood; (2) the extent of condition and extent of cause of risk significant performance issues were identified; and (3) corrective actions for risk significant performance issues are sufficient to address the root and contributing causes and prevent recurrence. The inspection consisted of examination of activities conducted under your license as they relate to safety, compliance with the Commission's rules and regulations, and the conditions of your operating license. The NRC concluded that, overall, the inspection objectives were met and that the combined effect of NextEra's completed and planned corrective actions were reasonable to address the related performance issues. Based on the results of this inspection, no findings were identified.

Given your acceptable performance in addressing the inadequate exercise critique process, and in accordance with the guidance in Inspection Manual Chapter (IMC) 0305, "Operating Reactor Assessment Program," the White finding will only be considered in assessing plant performance for a total of four quarters, and Seabrook Station will transition from the Regulatory Response Column of the NRC's Action Matrix to the Licensee Response Column on April 1, 2013.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.930 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publically Available Records System (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Anthony Dimitriadis, Chief Plant Support Branch 1 Division of Reactor Safety

Docket No: 50-443 License No: NPF-86

Enclosure:

Inspection Report 05000443/2013007

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